ML20086C514
| ML20086C514 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/30/1994 |
| From: | Ray D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 9507070122 | |
| Download: ML20086C514 (26) | |
Text
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Commonwealth Edirn n
, LaSalle County Nuclear Station 2601 N. 21st. Rd.
Marseilles,!!!inois 61341 Telephone 815/357-6761 August 29,1994 FILE COPY Ae;o -6 3 U.S. Nuclear Regulatory Commission coder _
Region ill 801 Warrenville Road RE d
Usle, Illinois 60532-4351 Attn: Chief Reactor Support Programs Branch
Dear Sir:
Enclosed is the Semi-annual Radioactive Fffluent Report for January through June,1994 for LaSalle County Nuclear Station, Docket Numbers o0-373 and 50-374.
Two copies of the report are provided for your use. Two copies will be forwarded to the Document Control Desk and one copy to the Senior Resident inspector.
Sincerely, L
D.J. Ray Station Manager LaSalle County Station DJR/TG/mkl Attachment cc:
Document Control Desk, U.S. NRC (2) lilinois Department of Nuclear Safety American Nuclear insurers DMEm-U.S. ' EPA bNMF_
Murray and Trettel, Inc.
/ '
Teledyne Isotopes Midwest Laboratory Chemistry Support (Downers Grove)
NRC Senior Resident inspector (LaSahe)
Site Quality Verification (LaSalle)
Central File lilini State Park EP File: EPG-01-R09 9507'd7'0122 940829 PDR ADOCK 05000373 p
PDR I\\
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LASALLE COUNTY NUCLEAR POWER STATION UNITS ONE AND TWO DOCKET NUMBERS 50-373 AND 50-374 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1994)
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated First Second Total Quarter Quarter Error %
A.
Fission and Activation Gases 1.
Total release ci 4.17E+01 1.17E-03 46%
2.
Average release rate for period uCi/sec 5.36E+00 7.50E-04 B.
Iodines 1.
Total iodine-131 Ci 2.20E-03 N/A 33%
2.
Average release rate for period uCi/sec 2.82E-04 N/A C.
Particulates 1.
Particulates with T1/2 >8 days Ci 1.06E-03 2.14E-04 2.
Average release rate for period uCi/sec 1.36E-04 2.75E-05 41%
3.
Gross alpha radioactivity (estimate) Ci
<1.00E-11 <1.00E-11 D.
Tritium 1.
Total release ci 4.43E+01 1.56E+01 18%
2.
Average release rate for period uCi/sec 9.02E+00 3.26E+00
"<" indicates activity of sample is less than LLD given in uci/ml 1 of 25 ZCADRAD/194
e EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1994)
GASEOUS EFFLUENTS-ELEVATED RELEASE Unit I and Unit 2 Continuous Mode First Nuclides Released January February March Quarter 1.
Fission Gases Ar-41 Ci
<1.79E-04
<1.00E-06
<1.00E-06 1.79E-04 Kr-85 Ci
<1.00E-06
<1.00E-06
<1.00E-06
<1.00E-06 Kr-85m Ci 5.95E+00
<1.00E-06
<1.00E-06 5.95E+00 Kr-87 Ci
<1.00E-06 9.30E+00
<1.00E-06 9.30E+00 Kr-88 Ci 2.65E+01
<1.00E-06
<1.00E-06 2.65E+01 Xe-131m Ci 1.44E-04
<1.00E-06
<1.00E-01 1.44E-04 Xe-133 Ci 1.12E-03 2.80E-04
<1.00E-06 1.40E-03 Xe-133m Ci
<1.00E-06
<1.00E-06
<1.00E-06
<1.00E-06 Xe-135 Ci 6.34E-04 2.07E-04
<1.00E-06 8.41E-04 Xe-135m Ci
<1.00E-06
<1.00E-06
<1.00E-06
<1.00E-06 i
Xe-138 Ci
<1.00E-06
<1.00E-06
<1.00E-06
<1.00E-06 Total for period Ci 3.24E+01 9.30E+00
<1.00E-06 4.27E+01 2.
I-131 Ci
<1.00E-11 1.57E-04 4.03E-05 1.97E-04 I-132 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 I-133 Ci 1.19E-04 1.58E-03 3.06E-04 2.00E-03 I-134 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 I-135 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 Total for period Ci 1.19E-04 1.73E-03 3.46E-04 2.20E-03 3.
Particulates Cr-51 Ci 2.60E-0(
<1.00E-11 2.60E-04 5.20E-04 Mn-54 Ci
<1.00L-11 9.18E-05
<1.00E-11 9.18E-05 Co-58 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 Fe-59 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 Co-60 Ci 4.90E-05 3.25E-04 7.83E-05 4.52E-04 Zn-65 Ci'
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 Sr-89 (Estimate)
Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 Sr-90'(Estimate)
Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 Nb-95 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 Mo-99 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 Cs-134 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 Cs-137 Ci
<1.00E-11
<1.00Eh11
<1.00E-11
<1.00E-11 Ba-140 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 La-140 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 Ce-141 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 Ce-144 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 Total for-period Ci 3.09E-04 4.16E-04 3.38E-04 1.06E-03
"<" indicates. activity of sample is less than LLD given uci/ml 1
i 2 of 25 ZCADRAD/194 i
a; r
i+
I EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1994) i' GASEOUS EFFLUENTS-ELEVATED RELEASE
. Unit 1 and Unit 2 continuous Mode Second Nuclides Released April May June Quarter 1.
Firsion Gases Ar-41 C1 1.13E-03
<1.00E-06
<1.00E-06 1.13E-03 I
Kr-85 Ci
<1.00E-06
<1.00E-06
<1.00E-06
<1.00E-06 Kr-85m Ci
<1.00E-06
<1.00E-06
<1.00E-06
<1.00E-06 i
Kr-87 Ci
<1.00E-06
<1.00E-06
<1.00E-06
<1.00E-06' Kr-88 Ci
<1.00E-06
<1.00E-06
<1.00E-06
<1.00E-06 l
Xe-131m Ci
<1.00E-06
<1.00E-06
<1.00E-06'
<1.00E-06 Xe-133 Ci
<1.00E-06
<1.00E-06
<1.00E-06
<1.00E-06 Xe-133m Ci
<1.00E-06
<1.00E-06
<1.00E-06
<1.00E-06 i
Xe-135 Ci
<1.00E-06 4.90E-05
<1.00E-06 4.90E-05 l
Xe-135m Ci
<1.00E-06
<1.00E-06
<1.00E-06
<1.00E-06 Xe-138 Ci
<1.00E-06
<1.00E-06 (1.00E-06
<1.00E-06 Total for period C1 1.13E-03 4.90E-05
<1.00E-06 1.17E-03 2.
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 I-132 Ci
<1.00E-11
<1.00E-11'
<1.00E-11
<1.00E-11 I-133 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11' I-134 Ci
<1.00E-12
<1.00E-11
<1.00E-11
.<1.00E-11 i
I-135 Ci
<1.00E-11
<1.00E-11
.<1.00E-11
<1.00E-11 l
Total for period Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11' -
.3.
Particulates Cr-51 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11.
Mn-54 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 f
Co-58 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 i
Fe-59 Ci
<1.00E-11
<1.00E-11'
<1.00E-11
<1.00E-11 l
Co-60 Ci
<1.00E-11
<1.00E-11 2.14E-04 2.14E-04 Zn-65 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 Sr-89 (Estimate)
Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 Sr-90 (Estimate)
Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 Nb-95 Ci
<1.00E-11
<1.00E-11'
<1.00E-11
<1.00E-11 Mo-99 Ci
<1.00E-11
<1.00E-11
<1.00E <1.00E-11 Cs-134 Ci
<1.00E-11
<1.00E-11
<1.00E-11 Cs-137 Ci
<1.00E-11
<1.00E-11
<1.00E-11
' <1.00E-11
[
<1.00E-11 i
Ba-140 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 i
La-140 Ci
<1.00E-11
<1.00E-11
<1.00E <1.00E-11 Ce-141 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 l
Ce-144 Ci
<1.00E-11
<1.00E-11
<1.00E-11
<1.00E-11 Total for' period Ci
<1.00E-11
<1.00E-11 2.14E-04 2.14E-04
"<" indicates. activity of sample is less than LLD given uci/ml 3 of 25 ZCADRAD/194 j
.s l
t EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REFORT (1994)
UNIT ONE LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES First Second i
Quarter Quarter A.
Fission and Activation Products 1.
Total release (not including Ci 0.00E+00 0.00E+00 tritium, gases, alpha) 2.
Average concentration released uCi/ml N/A N/A 3.
Maximum concentration released uCi/ml N/A N/A B.
Tritium 1.
Total release Ci 0.00E+00 0.00E+00 2.
Average concentration released uCi/ml N/A-N/A C.
Dissolved Noble Gases t
i 1.
Total release Ci 0.00E+00 0.00E+00 2.
Average concentration released uCi/ml N/A N/A' D.
Gross Alpha Radioactivity 1.
Total release Ci 0.00E+00 0.00E+00 2.
Average concentration released uCi/ml N/A N/A j
E.
Volume of Waste Released (prior to dilution) liters 0.00E+00 0.00E+00 F.
Volume of Dilution Water liters 0.00E+00 0.00E+00
"<" indicates activity of sample is less than LLD given in uCi/nd i
F P
P I
4 of 25 ZCADRAD/194
~
i a
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1994)
UNIT ONE BATCH MODE LIQUID EFFLUENTS First Nuclides Released January February March Quarter Cr-51 Ci Mn-54 Ci No No No No Fe-55 Ci Releases Releases Releases Releases Co-58 Ci Fe-59 Ci Co-60 Ci Zn-65 Ci l
Sr-89 Ci Sr-90 Ci Nb-95 Ci Zr-95 Ci Mo-99 Ci Tc-99m Ci I-131 Ci Cs-134 Ci Cs-137 Ci Ba-140 Ci La-140 Ci Ce-J41 Ci Ce-144 Ci Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci Xe-133m Ci Xe-133 Ci Xe-135m Ci Xe-135 Ci
"<" indicates activity of sample is less than LLD given in uCi/ml l
l 5 of 25 ZCADRAD/194
r EFFLUENT AND WACTE DISPOSAL SEMI-ANNUAL REPORT (1994)
UNIT ONE BATCH MODE LIQUID EFFLUENTS Second Nuclides Released April May June Quarter t
Cr-51 Ci No No No No Mn-54 Ci Releases Releases Releases Releases i
Fe-55 Ci Co-58 Ci i
Fe-59 Ci Co-60 Ci Zn-65 Ci Sr-89 Ci-Sr-90 Ci Nb-95 Ci Zr-95 Ci Mo-99 Ci l;
Tc-99m Ci I-131 Ci Cs-134 Ci Cs-137 Ci Ba-140 Ci La-140 Ci Ce-141 Ci Ce-144 Ci I
Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci l5 Xe-133m Ci Xe-133 Ci
- e-135m Ci Xe-135 Ci i
"<" indicates activity of sample is less than LLD given in uCi/ml
)
i l
l l
6 of 25 t
?CADRAD/194
'?
' ~ ' !. T i
l EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT'(1994)
UNIT TWO LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES i
First Second l
Quarter Quarter
{
A.
Fission and Activation Products f
1.
Total release-(not including Ci 0.00E+00 0.00E+00
[
tritium, gases, alpha)
'2.
Average concentration released uci/mi N/A.
N/A 3.
Maximum concentration released uCi/ml-N/A N/A
- j B.
Tritium i
1.
Total release ci 0.00E+00
~ 0.00E+00 2.
Average concentration released _
uCi/ml N/A N/A j
C.
Dissolved Noble Gases 1.
Total release
-Ci 0.00E+00 0.00E+00 2.
Average concentration released uCi/ml N/A N/A D.
Gross Alpha Radioactivity i
1.
Total release Ci 0.00E+00 0.00E+00 2.
Average concentration released uCi/ml N/A N/A j
E.
Volume of Waste Released liters 0.00E+00 0.00E+00 F.
Volume of Dilution Water liters 0.00E+00 0.00E+00
[
"<" indicates activity of sample is less than LLD.given in'uci/ml l
-l t
i i
~l i
i
~
l r
~
i 7 of 25 1
ZCADRAD/194 4
l
hf W
[
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1994)
UNIT TWO SATCH MODE LIQUID EFFLUENTS First Nuclides Released January February March Quarter Cr-51 Ci Mn-54 Ci No No No No L
Fe-55 Ci Releases Releases Releases Releases co-58 Ci Fe-59 Ci Co-60 Ci Zn-65 Ci Sr-89 Ci Sr-90 Ci Nb-95 Ci Zr-95 Ci Mo-99 Ci Tc-99m Ci I-131 C1 Cs-134 Ci Cs-137 Ci Ba-140 Ci La-140 Ci Ce-141 Ci Ce-144 Ci Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 4'
Xe-133m Ci Xe-133 Ci i
Xe-135m Ci Xe-135 Ci
"<" indicates activity of sample is less than LLD given in uCi/ml l
~
l l
l i
1 8 of 25 ZCADRAD/194
EFFLUENT AND WASTE DISPCSAL SEMI-ANNUAL REPORT (1994)
UNIT TWO BATCH MODE LIQUID EFFLUENTS Second Nuclides Released April May June Quarter Cr-51 Ci No No No No Mn-54 Ci Releases Releases Releases Releases Fe-55 Ci co-58 Ci Fe-59 Ci Co-60 Ci Zn-65 Ci Sr-89 Ci Sr-90 Ci Nb-95 Ci Zr-95 Ci Mo-99 Ci 2.
Tc-99m Ci
~ !
I-131 Ci Cs-134 Ci Cs-137 Ci Ba-140 Ci La-140 Ci Ce-141 Ci Ce-144 Ci Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci Xe-133m Ci i
Xe-133 Ci Xe-135m Ci Xe-135 Ci
"<" indicates activity of sample is less than LLD givan in uCi/ml b
9 of 25 ZCADRAD/194
I EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1994)
MAXIMUM-DOSES RESULTING FROM RELEASES First Second Quarter Quarter A.
Gaseous Effluents (Units One and Two) 1.
Gamma air mrad 1.32E-03 2.69E-08 2.
Beta air mrad 4.43E-05 9.24E-10 3.
Total body mrem 1.00E-03 2.02E-08 4.
Skin mrem 1.06E-03 2.15E-08 5.
Organ (infant thyroid) mrem 0.00E+00 0.00E+00 B.
Liquid Effluents (Unit One) 1.
Total body mrem 0.00E+00 0.00E+00 4.
Internal organ (adult liver) mrem 0.00E+00 0.00E+00 C.
Liquid Effluents (Unit Two) 1.
Total body mrem 0.00E+00 0.00E+00 4.
Internal organ mrem 0.00E+00 0.00E+00 COMPLIANCE STATUS A.
Gaseous Effluents (Units One and Two) 1.
Gamma air
% of Tech. Spec. Limit 0.03 0.00 2.
Beta air
% of Tech. Spec. Limit 0.00 0.00 3.
Total body
% of Tech. Spec. Limit 0.04 0.00 4.
Skin
% of Tech. Spec. Limit 0.01 0.00 5.
Organ
% of Tech. Spec. Limit 0.00 0.00 i
B.
Liquid Effluents (Unit One) 1.
Total body
% of Tech. Spec. Limit 0.00 0.00 2.
Internal organ
% of Tech. Spec. Limit 0.00 0.00 C.
Liquid Effluents (Unit Two) 1.
Total body
% of Tech. Spec. Limit 0.00 0.00 2.
Internal organ (adult liver)
% of Tech. Spec. Limit 0.00 0.00 The maximum dose resulting from releases include nuclides with half-lives less than eight days.
l 10 of 25 ZCADRAD/194
n_
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1994)
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL First' January February March Quarter 1.
Spent resins, filter sludges, evaporator bottoms, etc.
a.
Quantity shipped cu.m.
1.64E+01 4.59E+01 2.83E+01 9.06E+01 b.
Total activity Ci 2.36E+01 6.43E+02 6.17E-01 6.67E+02 c.
Major nuclides (estimate)
Mn-54 9
8 7
Fe-55 54 54 75 Co-58 1
1 1
{
Co-60 33 33 17 1
d.
Container volume cu.m.
4.83E+00 4.33E+00 2.36E+00 5.82E+00 5.82E+00 4.33E+00 i
2.36E+00 1
f.
Solidification agent Cement Cement Cement 2.
Dry compressible waste,
)
contaminated equipment, etc.
I a.
Quantity shipped cu.m.
0.00E+00 7.24E+01 2.43E+02 3.15E+02 b.
Total activity Ci 0.00E+00 3.84E-01 1.48E+00 1.86E+00 c.
Major nuclides (estimate)
Cr-51 0
5 5
Mn-54 0
15 15 Fe-55 0
55 55 Fe-59 0
6 3
Co-60 0
15 15 d.
Container type N/A LSA LSA e.
Container volume cu.m.
N/A 7.24E+01 7.24E+01 1.70E+02 1
i i
l l
l l
l l
l l
11 of 25 ECADRAD/194
. ::9 u t
,.=
E c
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1994)
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL First' January February March-
.QuarterL 3.
Other D
a.
Quantity shipped cu.m.
0.00E+00' 0.00E+00- 0.00E+00 0;00E+00 b.
Total activity.
Ci 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 c.
Major nuclides (estimate):
Cr-51 0
0 0
Mn-54 0
0 0
Fe-55 0
.0 0
Fe-59 0
0 0
co-60 0
0 0
d.
Container type N/A N/A N/A e.
Container volume cu.m.
N/A N/A N/A 4.
Irradiated Components a.
Number of shipments 0
0 0
0 b.
Mode of-Transportation N/A N/A N/A i
c.
Destination N/A N/A N/A
- i 5.
Solid Waste Disposition i'
a.
Number of Shipments 3
10 9
'22 l
b.
Mode of Transportation Truck Truck Truck Number 3
10 9
i c.
Destination Oak Ridge, TN Oak Ridge, TN Oak Ridge, TN Number 0
1 1
i Barnwell,'SCBarnwell, SCBarnwell, SC Number 3
9 8
I l
I i
f I
i I
t i
I 12 of 25 j
ZCADRAD/194 i
4 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1994)
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL Second April'
'May June Quarter 1.
Spent resins, filter sludges, evaporator bottone, etc.
a.
Quantity shipped cu.m.
6.80E+00 2.41E+01 1.78E+01 4.87E+01 b.
Total activity Ci 5.67E-02 4.95E-01 3.22E-01 8.73E-01 c.
Major nuclides Mn-54 6
7 7
Fe-55 22 64 68
.{
co-58 9
1 0
Co-60 59 26 23 d.
Container volume cu.m.
3.40E+00 4.33E+00 4.83E+00 5.82E+00 2.36E+00 2.36E+00 3.40E+00 f.
Solidification agent Cement Cement Cement 2.
Dry compressible waste, contaminated equipment, etc.
a.
Quantity shipped cu.m.
1.44E+02 2.46E+01 1.35E+02 3.03E+02 b.
Total activity Ci 2.27E-01 9.50E-02 7.17E+00 7.49E+00 c.
Major nuclides (estimate)
Mn-54 15 15' 15 Fe-SS 54 54 58 Fe-59 7
7 4
Co-60 15 15 16 d.
Container volume cu.m.
7.24E+01 2.46E+01 4.88E+00 4.83E+00 2.46E+01 1.52E+01 3.62E+01 13 of 25 ZCADRAD/194
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1994)
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL Second April M
June Quarter y
3.
Other a.
Quantity shipped cu.m.
0.00E+00 0.00E+00 0.00E+00 0.00E+00 b.
Total activity Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
c.
. Major nuclides (estimate)
Mn-54 0
0 0
Fe-55 0
0 0
Fe-59 0
0 0
Co-60 0
0 0
d.
Container type N/A N/A N/A e.
Container volume cu.m.
N/A N/A N/A 4.
Irradiated Components a.
_. Number of shipments 0
0 2
b.
Mode of Transportation N/A N/A Truck c.
Destination N/A N/A Barnwell, SC 5.
Solid Waste Disposition a.
Number of Shipments 4
6 14 24 b.
Mode of Transportation Truck Truck Truck Number 4
6 14 c.
Destination Oak Ridge, TN Oak Ridge, TN Oak Ridge, TN Number 2
1 3
Barnwell, SC Barnwell, SC Barnwell, SC Number 2
5 11 I
i 14 of 25 ZCADRAD/194
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1994)
I Supplemental Information 1.
Regulatory Limits a.
Gaseous Effluents 1)
The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site shall be limited to the following:
a)
During any calendar quarter:
Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and b)
During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
2)
The dose to an individual from radioiodines and radioactive materials in particulate form, and radionuclides, other than noble gases, with half-lives greater than eight days in gaseous effluents released, from each reactor unit, from the site shall be limited to the following:
a)
During any calendar quarter: Less than or equal to 7.5 mRems to any organ, and b)
During any calendar year:
Less than or equal to 15 mRems to any organ.
b.
Liquid Effluents 1)
The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site shall be limited:
a)
During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and b)
During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
c.
Total Dose 1)
The dose or dose commitment to any member of the public, due to releases or radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.
15 of 25 ZCADRAD/194
G L i
t t
-EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1994)
Supplemental Information (continued)
.- a 2.
Maximum Permissible Concentrations
. l
'a.
Gaseous Effluents i
1)
The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to the following:
}
.a)
. For noble gases: Less than or equal to 500 mrem / year to
'the total body and less than or equal to 3000 mrem / year' to the skin, and
(
b)
For all radiciodines and for all radioactive materials in particulate form, and radionuclides, other than noble gases, with half-lives greater than eight days:
Less I
than or equal to 1500 mrem / year to any organ via the inhalation pathway.
t >
t b.
Liquid Effluents 1)
The concentration of radioactive material released form the site shall be limited to the concentrations specified in 10
' CFR Part 20, Appendix B, Table II, Column 2 for radionuclides 4
other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be. limited to the following:
Nuclide MPC (pci/ml)
Kr-85m 2.00E-04 Kr-85 5.00E-04 Kr-87 4.00E-05 Kr-88 9.00E-05 Ar-41 7.00E-05 Xe-131m 7.00E-04 Xe-133m 5.00E-04 Xe-133 6.00E-04 Xe-135m 2.00E-04 Xe-135 2.00E-04 3.
Average Energy a.
Not Applicable.
4.
Measurements and Approximations of Total Radioactivity a.
Gaseous Effluents li Containment Vent and Purge System is sampled by grab sample which is analyzed for principal gamma emitters and H-3.
2)
Main Vent Stack is sampled by grab sample which is analyzed for principal gamma emitters and H-3.
3)
Standby Gas Treatment System is sampled by grab sample which is analyzed for principal gamma emitters.
16 of 25 ZCADRAD/194 p
-w
r
-t:
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1994)
Supplemental Information (continued)
-4)
All release types.as listed in 1 and 2 above, ~ at the vent
-stack and as listed in 3 above,. at the Standby Gas Treatment System whenever there is a flow, are continuously sampled by charcoal, particulate and composite samples which are analyzed for iodines, principal ganna emitters, gross alpha, Sr-89 and Sr-90.
Noble gases, gross beta and gansna are continuously y
monitored by noble gas monitors for the vent stack and the standby gas treatment system.
b.
Liquid Effluents 1)
Batch waste release tanks are sampled each batch for principal gamma emitters, I-131, dissolved and entrained noble gases,
[.
H-3, gross alpha, Sr-89, Sr-90 and Fe-55, 2)
Continuous releases are sampled continuously in proportion to the rate of flow of the effluent stream and by grab sample.
Samples are analyzed ' for principal gamma emitters, I-131, dissolved and entrained noble gases, H-3, gross alpha, Sr-69, Sr-90 and Fe-55.
5.
Batch Releases a.
Gaseous 1)
Number of batch releases:
None j
2)
Total time period for batch releases:
N/A 3)
Maximum time period for a batch release:
N/A 4)
Average time period for batch releases:
N/A 5)
Minimum time period for a batch release:
N/A b.
Liquid 1)
Number of batch releases:
N/A 2)
Total time period for batch releases:
N/A 3)
Maximum time period for a batch release:
N/A 4)
Average time period for batch releases:
N/A 5)
Minimum time period for a batch release:
N/A 6)
Average stream flow during periods of release of effluent into a flowing stream:
N/A
~!
1 1
17 of 25 ZCADRAD/194
\\
EFFLUENT-AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1994)
Supplemental Information (continued) 6.
Abnormal Releases a.
Gaseous 1)
Number of releases:
None 2)
Total activity released:
N/A b.
Liquid 1)
Number of releases:
None 2)
Total activity released:
N/A i
f ZCADRAD/194
a e
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1994)
METEOROLOGICAL DATA t
?
(See following pages.)
5 l
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t 19 of 25 ZCADRAD/194 J
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~
-o 0
Process Control Program (PCP) Changes The solidification formula used by LaSalle Station's Radwaste processing vendor was amended to allow greater packaging efficiency. This amendment constitutes a change to the PCP as defined by the station's PCP (LaSalle Station procedure LAP-200-6).
An on-site review (OSR number 93-65), per LAP-1200-2, and a 50.59 Safety Evaluation, per LAP-1200-13, were performed prior to implementstion of the change.
The changed involved the reduction of the amount of solidification agent used to pro ass defined types of radwaste.
The reduction allows for higher waste loadings in the processed containers.
Stability of the final waste form is conferred by the container itself (i.e. Polyethylene HIC) used in conjunction with a concrete caisson, therefore stability of the package is not impacted.
l i
l ZCADRAD/194
o 1993 Semi-Annual Effluent Report Errata During a NRC Audit conducted July 11,.1994 through August 5, 1994, it was determined that both Semi-Annual Effluent Reports from LaSalle Station for 1993 inadvertently included nuclides with less than eight day half-lives.
This is contrary to the requirements for the ODCM Semi-Annual Effluent Report.
The 1993 Semi-Annual Effluent Report data on pages 2 and 3 listing the gaseous effluent isotopes, particulate section, and on page 10, listing the maximum dose resulting from release, section for gaseous effluents, were the effected pages of the report.
The isotopes listing, pages 2 and 3, include isotopes with half-lives less than eight days, thereby indicating higher Curie totals for the period than were i
actually experienced. The maximum dose resulting from the release, page.10, used t
the isotope data, thereby indicating higher dose totals for the period than were l
actually e:cperienced.
The ODCM effluent data for LaSalle Station for 1993 will be corrected, recalculated and the correct results re-distributed by October 31, 1994.
I
{
l i
l l
l l
25 of 25 ZCADRAD/194 l
l